| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 1.599 (b) | 1.750 (b) | 1.094 | − | 2.108 (b) | 2.822 (b) |
| 2 | (n,elastic) | 1.166 (b) | 1.317 (b) | 1.129 | − | 993.8 (mb) | 2.710 (b) |
| 4 | (n,inelastic) | ( E-thr = 1.774 MeV ) | 597.8 (mb) | 110.1 (mb) | |||
| 16 | (n,2n) | ( E-thr = 10.59 MeV ) | 362.5 (mb) | 73.78 (μb) | |||
| 22 | (n,na) | ( E-thr = 8.062 MeV ) | 2.724 (mb) | 504.0 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.611 MeV ) | 83.43 (mb) | 49.69 (μb) | |||
| 32 | (n,nd) | ( E-thr = 16.49 MeV ) | − | 1.298 (nb) | |||
| 102 | (n,γ) | 432.9 (mb) | 433.2 (mb) | 1.001 | 203.3 (mb) | 286.8 (μb) | 549.8 (μb) |
| 103 | (n,p) | ( E-thr = 4.182 MeV ) | 23.92 (mb) | 383.5 (μb) | |||
| 104 | (n,d) | ( E-thr = 6.327 MeV ) | 6.491 (mb) | 6.024 (μb) | |||
| 105 | (n,t) | ( E-thr = 10.06 MeV ) | 589.9 (μb) | 142.6 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 14.08 MeV ) | − | 9.236e-12 (b) | |||
| 107 | (n,a) | ( E-thr = 1.319 MeV ) | 35.26 (mb) | 957.0 (μb) | |||
|
These cross sections are calculated from JENDL-4.0 at 300K.
The background color of each cell noted a cross section means the order of the cross-section value.
The unit of cross section, (b), means barns, and SI prefixes are used as following.
(kb) → 103(b), (mb) → 10−3(b),
(μb) → 10−6(b), (nb) → 10−9(b).
MT is a number that defines a reaction type. For the relation between MT and reaction type, please see here or refer to the manual of ENDF formats.
Maxwellian Average :
where T denotes the temperature, and kB the Boltzmann constant.
The upper and lower limits of integration, EL and EU
are set to 10−5 eV and 10 eV, respectively.
Resonance Integral :
with EL = 0.5 eV and EU = 10 MeV.
U-235 Thermal Fission-Neutron Spectrum Average (Fiss. Spec. Average) :
with EL = 10−5 eV and EU = 20 MeV.
The parameters a and b are 0.988 MeV and 2.249 MeV−1, respectively.
Westcott g-factor :
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